ML20137A558
| ML20137A558 | |
| Person / Time | |
|---|---|
| Site: | 05000072 |
| Issue date: | 03/14/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137A512 | List: |
| References | |
| NUDOCS 9703200375 | |
| Download: ML20137A558 (2) | |
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%,..... j' SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE ORDER TERMINATING AMENDED FACILITY OPERATING LICENSE N0. R-25 UNIVERSITY OF UTAH AGN-201 RESEARCH REACTOR DOCKET N0. 50-72
1.0 INTRODUCTION
By letter dated July 17, 1990, as supplemented on July 18, 1990, and June 12, 1991, the University of Utah (the licensee) submitted a plan for dismantlement and decontamination of its AGN-201 Research Reactor (AGN-201 or the reactor).
The letter of July 17, 1990, contained a request for termination of Amended Facility Operating License No. R-25 upon successful completion of decommissioning.
Following review by the NRC staff, the plan was approved on August 1, 1991, and the licensee commenced dismantlement and decontamination.
Upon completion of the dismantlement and decontamination, the licensee submitted by letter dated April 13, 1994, as supplemented on March 17 and 22, 1995, and February 6,1996, "A Summary of the Decommissioning Process of the University of Utah AGN-20lM Reactor No. 107" as a basis for license termination.
On April 9, 1996, Oak Ridge Institute for Science and Education (0 RISE) representatives performed a confirmatory survey at the facility under an interagency agreement and in accord.ance with a request for technical assistance from NRC Region IV.
Region IV staff members accompanied the 0 RISE personnel and observed the confirmatory survey.
By separate action, the NRC has granted, upon its own initiative, a specific exemption in accordance with 10 CFR 50.12 to the part of the requirements of 10 CFR 50.82(b)(6)(ii), that requires a terminal radiation survey and associated documentation to demonstrate that the site is suitable for release as a condition of license termination.
The University of Utah operates the TRIGA Research Reactor (Docket No. 50-407, Facility Operating License No.
R-126) in the same room where the AGN-201 is located. The Reactor Room of the Merrill Engineering Building remains subject to the TRIGA license. Therefore, there is no site to be released for unrestricted use as part of the termination of the AGN-201 license. All that remains on the AGN-201 license are reactor components that are to be released for unrestricted use.
The NRC will consider release of the Reactor Room in the future when the licensee applies for termination of the TRIGA license and conducts a terminal survey to show compliance with the regulation before release of the site.
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2.0 EVAL.UATION In a memorandum dated July 15, 1996, from Thomas P. Gwynn, Director, Division
'of Reactor Safety, Region IV, to Seymour H. Weiss, Director, Non-Power j
Reactors and Decommissioning Project Directorate, Office of Nuclear Reactor Regulation, Region IV concluded on the basis of a review of licensee and ORISE survey results that (1) residual surface contamination levels for reactor components were less than the values in NRC Regulatory Guide 1.86, Table 1; j
(2) gamma radiation levels associated with reactor components were less than j
j-5 micro-res/hr above background at 1 meter from component surfaces; and.
(3) all. byproduct and special nuclear material on Facility License No. R-25 4
i was properly disposed of or transferred to another licensee authorized to receive the material. On the basis of the Region IV review of the survey
- results, Region IV recommended that the AGN-201 reactor components be released for unrestricted use and that Facility License No. R-25 be terminated.
.The staff has determined that (1) the residual contamination levels for the reactor comply with the criteria of Regulatory Guide 1.83, Table 1, which establish acceptable residual surface contamination levels for release for unrestricted use and-termination of the license; (2) the direct radiation levels are below 5 micro-rem /hr above background at I meter, which is the t
exposure limit established by the NRC staff as acceptable for release for i
unrestricted use and termination of the license; and (3) material licensed under Amended Facility Operating License No. R-25 has been removed from the site or transferred to other authorized licensees.
The staff further has determined that the site will remain subject to Operating License No. R-126 4
i for the TRIGA at the same location.
Therefore, the staff concludes that the i.
facility can be released for unrestricted use and Amended Facility Operating License No. R-25 can be terminated.
3.0 ENVIRONMENTAL CONSIDERATION
The Commission has prepared an environmental assessment and finding of no significant impact (EA), which was published in the Federal Reaister on March 13, 1997 (62 FR 11935)
On the basis of the EA and the above safety evaluation, the Commission has determined that no environmental impact statement is required and that issuance of this Order terminating the license will have no significant adverse effect on the quality of the human environment.
4.0 CONCLUSION
On the basis of the foregoing considerations, the staff concludes that Amended Facility Operating License No. R-25 can be terminated without undue risk to the health and safety of the public or workers, and without any significant impact on the public or the environment.
Principal Contributor: Alexander Adams, Jr.
Date:
March 14, 1997